Predictive simulations of ITER including neutral beam driven toroidal rotation

Halpern, Federico David; Kritz, A.H.; Bateman, G.; Pankin, A.Y.; Budny, R.; McCune, D.

doi:10.1063/1.2931037

Cited by 39 publications

(51 citation statements)

References 32 publications

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“…This investigation will ignore speculation on turbulent generation of poloidal rotation and any ρ * scaling of such effects. Predictive transport run 20100N05 at 245 seconds has been investigated recently [49] for predictions of ITER performance with coupled PTRANSP [5,7]-TGLF [50], and contrasted with previous predictions using GLF23 [4,51]. The results of Budny et al [49] displayed prediction of core T e , T i with a higher sensitivity to the E × B shearing rate than previous GLF23 simulations, hence modifications to the core E r will be more pronounced within the new, more accurate TGLF modeling.…”

Section: Discussion Of Effect Anomalous Poloidal Rotation Has On E × mentioning

confidence: 99%

“…As toroidal rotation is lowered by reduced net torque, the benefit of the large shearing rate provided by rapid toroidal rotation decreases [3]. Predictions of ITER with GLF23 [4,5] and the more recent TGLF [6] indicate a significant increase in fusion performance with increased E×B shear, however in devices with low relative torque the benefits of the large toroidal rotation may be absent. The core E r will be determined by the contributions from the pressure gradient, toroidal rotation and poloidal flow, all having similar magnitude [7].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Collisionality scaling of main-ion toroidal and poloidal rotation in low torque DIII-D plasmas

Grierson¹,

Burrell²,

Solomon³

et al. 2013

Nucl. Fusion

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Abstract. In tokamak plasmas with low levels of toroidal rotation, the radial electric field E r is a combination of pressure gradient and toroidal and poloidal rotation components, all having similar magnitudes. In order to assess the validity of neoclassical poloidal rotation theory for determining the poloidal rotation contribution to E r , D α emission from neutral beam heated tokamak discharges in DIII-D [J.L. Luxon, Nucl. Fusion 42, 614 (2002)] has been evaluated in a sequence of low torque (electron cyclotron resonance heating and balanced diagnostic neutral beam pulse) discharges to determine the local deuterium toroidal rotation velocity. By invoking the radial force balance relation the deuterium poloidal rotation can be inferred. It is found that the deuterium poloidal flow exceeds the neoclassical value in plasmas with collisionality ν * i < 0.1, being more ion diamagnetic, and with a stronger dependence on collisionality than neoclassical theory predicts. At low toroidal rotation, the poloidal rotation contribution to the radial electric field and its shear is significant. The effect of anomalous levels of poloidal rotation on the radial electric field and cross-field heat transport is investigated for ITER parameters.

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Section: Discussion Of Effect Anomalous Poloidal Rotation Has On E × mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Collisionality scaling of main-ion toroidal and poloidal rotation in low torque DIII-D plasmas

Grierson¹,

Burrell²,

Solomon³

et al. 2013

Nucl. Fusion

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“…The PTRANSP code [5][6][7][8] is used to generate predictions of ITER plasmas for use as benchmarking cases. The cases are listed in Table I.…”

Section: Benchmark Casesmentioning

confidence: 99%

“…The PTRANSP code [5][6][7][8] is used to generate predictions for the plasma conditions. The predictions are integrated and self-consistent in that the heating, current-drive, and beam torques are calculated using predicted plasma profiles.…”

Section: Appendix 1 -Ptransp Predictions Of the Benchmark Casesmentioning

confidence: 99%

Benchmarking ICRF Full-wave Solvers for ITER

2011

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Benchmarking of full-wave solvers for ICRF simulations is performed using plasma profiles and equilibria obtained from integrated self-consistent modeling predictions of four ITER plasmas. One is for a high performance baseline (5.3 T, 15 MA) DT H-mode. The others are for half-field, half-current plasmas of interest for the pre-activation phase with bulk plasma ion species being either hydrogen or He 4 . The predicted profiles are used by six full-wave solver groups to simulate the ICRF electromagnetic fields and heating, and by three of these groups to simulate the current-drive.Approximate agreement is achieved for the predicted heating power for the DT and He 4 cases. Factor of two disagreements are found for the cases with second harmonic He 3 heating in bulk H cases. Approximate agreement is achieved simulating the ICRF current drive.

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“…Previous PTRANSP papers [8][9][10] use physics-based models to predict profiles of the temperatures T e and T i , and in some cases, the toroidal rotation v tor . The models used are the GLF23 model [13,14] and the MMM08 model [15,16] (a modified version of Weiland model [17]).…”

Section: Plasmas Studiedmentioning

confidence: 99%

Current control in ITER steady state plasmas with neutral beam steering

Budny

2010

Physics of Plasmas

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Predictions of quasi steady state DT plasmas in ITER are generated using the PTRANSP code. The plasma temperatures, densities, boundary shape, and total current (9 -10 MA) anticipated for ITER steady state plasmas are specified. Current drive by negative ion neutral beam injection, lower-hybrid, and electron cyclotron resonance are calculated. Four modes of operation with different combinations of current drive are studied. For each mode, scans with the NNBI aimed at differing heights in the plasma are performed to study their effects on current control on the q profile. The time-evolution of the currents and q are calculated, and long-duration transients (up to ≃ 1500 s) are predicted. Effects of the beam and alpha ion pressures on the MHD equilibrium are predicted to significantly alter the bootstrap current. The TEQ equilibrium solver is found to be much more accurate than the VMEC solver. Quasi steady state, strongly reversed q profiles are predicted for some beam injection angles when the current drive and bootstrap currents are sufficiently large.

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Predictive simulations of ITER including neutral beam driven toroidal rotation

Cited by 39 publications

References 32 publications

Collisionality scaling of main-ion toroidal and poloidal rotation in low torque DIII-D plasmas

Collisionality scaling of main-ion toroidal and poloidal rotation in low torque DIII-D plasmas

Benchmarking ICRF Full-wave Solvers for ITER

Current control in ITER steady state plasmas with neutral beam steering

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